Hydrogen Inventory Simulations for PFCs (HISP)
Kaelyn Dunnell, Adria Lleal, Etienne Augustin Hodille, Jonathan Dufour, Remi Delaporte-Mathurin, Tom Wauters

TL;DR
HISP is an open-source simulation tool that models hydrogen isotope inventory in plasma-facing components of fusion devices, evaluating T removal strategies like baking, GDC, and DD pulses.
Contribution
This paper introduces HISP, a novel open-source tool that integrates plasma code outputs with 1D hydrogen transport models for fusion device components.
Findings
Baking effectively reduces T inventory by 88% in tungsten divertor.
GDC peaks at 23% T removal efficiency in tungsten FW.
DT operation results in approximately 35 g of T in components after 10 days.
Abstract
Hydrogen Inventory Simulations for Plasma facing components (HISP) is an open-source simulation tool to model the evolution of hydrogen (H) isotopes inventory in plasma-facing-components (PFCs) of magnetic confinement fusion devices. The objective was to produce a demonstrative study describing the efficiency of tritium (T) removal strategies in ITER. HISP transforms plasma code outputs to spatial-averaged inputs along ITER's first wall (FW) and divertor for 1D H transport models using FESTIM. Exposure conditions were tested in three scenarios that included DT operation and varied T removal methods. Generally, DT operation resulted in \SI{35}{g} of T in FW and divertor components after 10 days of DT pulses. Almost \SI{80}{\%} of the total T inventory resided in co-deposited boron layers in the divertor. Baking proved to be the most effective T removal method in the divertor,…
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